Corrigendum to “Ceramic coating for corrosion (c3) resistance of nuclear fuel cladding” [Surf. Coat. Technol. (2015) 133–143]

Alat, Ece; Motta, Arthur T.; Comstock, R. J.; Partezana, Jonna M.; Wolfe, Douglas E.

doi:10.1016/j.surfcoat.2016.07.019

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Surface and Coatings Technology

2016

DOI: 10.1016/j.surfcoat.2016.07.019

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Corrigendum to “Ceramic coating for corrosion (c3) resistance of nuclear fuel cladding” [Surf. Coat. Technol. (2015) 133–143]

Ece Alat

Arthur T. Motta

R. J. Comstock

et al.

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2023

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Protective Vacuum-Arc Coatings on Zirconium Alloy Fuel Cladding to Prevent Catastrophic Accidents at Nuclear Reactors

Куприн¹,

Zuyok²,

Белоус³

et al. 2023

Problems of Atomic Science and Technology

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The processes of vacuum arc deposition of multicomponent coatings based on Cr, Ti, Al, Fe, Y, Si, and their nitrides with a thickness of 5…9 µm for the protection of zirconium alloy fuel rods were developed. The composition, structure, and mechanical properties of the coatings were determined by electron microscopy, energy dispersive X-ray spectroscopy, X-ray diffraction analysis, and nanoindentation. Comparative studies of the protective properties of coatings during high-temperature oxidation of Zr1Nb tubes were carried out. It was found that metal coatings with a high chromium content have excellent protective properties during tests under simulated accident conditions. They are simultaneously resistant to high-temperature corrosion in air at 750…1100 °C and in water steam during thermal cycling up to 1020 °C. Hard nitride coatings, which significantly strengthen the surface of the zirconium alloy and provide good protection against oxidation in air, are less effective in water steam under thermal cycling. The coatings and processes of synthesis developed at NSC KIPT can be useful for improving fuel cladding made of zirconium alloys of the world's leading nuclear fuel producer Westinghouse Electric Company.

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Protective Vacuum-Arc Coatings on Zirconium Alloy Fuel Cladding to Prevent Catastrophic Accidents at Nuclear Reactors

Куприн¹,

Zuyok²,

Белоус³

et al. 2023

Problems of Atomic Science and Technology

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show abstract

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Corrigendum to “Ceramic coating for corrosion (c3) resistance of nuclear fuel cladding” [Surf. Coat. Technol. (2015) 133–143]

Cited by 1 publication

References 0 publications

Protective Vacuum-Arc Coatings on Zirconium Alloy Fuel Cladding to Prevent Catastrophic Accidents at Nuclear Reactors

Protective Vacuum-Arc Coatings on Zirconium Alloy Fuel Cladding to Prevent Catastrophic Accidents at Nuclear Reactors

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